Neutron shielding qualities and gamma ray buildup factors of concretes containing limonite ore

Oto, Berna; Yıldız, Nergiz; Korkut, Turgay; Kavaz, Esra

doi:10.1016/j.nucengdes.2015.07.060

Cited by 68 publications

(25 citation statements)

References 28 publications

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“…Thus, the Mn-composite exhibits two bands at 9130 and 14 925 cm À1 . These are assigned to spin allowed transitions 5 The very broad EPR signal observed for all samples highlights the FeO(OH) strong ferromagnetic properties at low temperature. By increasing the temperature, the ferromagnetic properties vanish slowly, which is pointed out in Fig.…”

Section: Uv-vis-nir Spectroscopy Characterizationmentioning

confidence: 77%

“…3,4 Some concrete based on limonite or ilmenite-limonite is used as nuclear reactor shielding. [5][6][7] Both goethite and limonite are used as precursors for preparing many functional materials such as magnetic oxides, maghemite, magnetite, and ferrites. [8][9][10] Moreover, the limonite addition to lithium-ion batteries increases the ionic resistance and conductivity.…”

Section: Introductionmentioning

confidence: 99%

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Soft synthesis and characterization of goethite-based nanocomposites as promising cyclooctene oxidation catalysts

et al. 2021

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Section: Uv-vis-nir Spectroscopy Characterizationmentioning

confidence: 77%

Section: Introductionmentioning

confidence: 99%

Soft synthesis and characterization of goethite-based nanocomposites as promising cyclooctene oxidation catalysts

et al. 2021

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“…Therefore, both values show completeindependence on chemical compositions of gypsum at the intermediate energy range. At the high energy range, both values decreased because thepair production was dominant producing electron-positron pair [15,16]. Such process prevented photons from accumulating in the medium.…”

Section: Buildup Factormentioning

confidence: 98%

Coconut Dust Gypsums Board Building Material for Shielding Radiation and Buildup Factors

Sriwongsa

Ravangvong

Sangthon

et al. 2021

Walailak J Sci & Tech

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The coconut dust gypsums were fabricated and investigated through shielding radiation properties, energy absorption buildup factor (EABF), and exposure buildup factor (EBF). The mass attenuation coefficient (mm) was investigated by using the Compton scattering technique at energy 662 keV and theoretical values of the mass attenuation coefficients were computed by using the WinXCom software program at different photon energies from 1 keV - 100 GeV. EABF and EBF values were computed by the Geometric Progression (G-P) fitting method at photon energies ranging between 0.015 and 15 MeV up to deep penetration of 40 mean free path (mfp). After the addition of coconut dust volume into gypsum board, it was found that mm values of the experiment and theory were generally in a good agreement. The results also indicated that the mm increased while the EABF and EBF decreased along with the increase in the coconut dust volume. The EABF and EBF values with photon energy and deep penetration for coconut dust gypsums were found at a minimum value, i.e., at low and high energy range whereas, at the intermediate energy range, it could become high. These results suggest that coconut dust gypsums can be used as shielding radiation building material.

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“…Sehingga diperlukan unsur-unsur tambahan di dalam perisai radiasi yang dapat menahan atau menangkap neutron secara efektif. Diantara unsur-unsur tambahan tersebut yang dapat menangkap radiasi neutron dengan sangat baik adalah boron, cadmium dan lain-lain yang memiliki tampang lintang tangkapan neutron yang besar [12,13,14]. Pada penelitian ini digunakan beton yang mengandung senyawa boron [15,16,17] sebagai perisai radiasi tambahan di depan tabung berkas yaitu jenis beton Boron Frits-baryte setebal 280 cm.…”

Section: Jarak Radial Dari Tengah Teras (Cm)unclassified

Desain Konseptual Perisai Radiasi Reaktor Rri-50

Hamzah

Kuntoro

2015

Tri Dasa Mega

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ABSTRAKDESAIN KONSEPTUAL PERISAI RADIASI REAKTOR RRI-50. Salah satu parameter yang harus dipenuhi dalam mendesain reaktor nuklir adalah desain perisai radiasi yang dapat menjamin keamanan dan keselamatan radiasi bagi pekerja dan masyarakat sekitar. Pada penelitian ini dilakukan desain perisai radiasi RRI-50 dengan elemen bakar berjenis U9Mo-Al berkerapatan tinggi dengan tipe pelat sebanyak 21 buah dan berdimensi seperti elemen bakar RSG-GAS tapi panjang aktifnya 70 cm. Konfigurasi teras terdiri dari 16 elemen bakar dan 4 elemen kendali serta 5 posisi iradiasi sehingga membentuk matriks 5 x 5. Tujuan dari penelitian ini adalah mendesain perisai radiasi dan menentukan distribusi laju dosis di daerah kerja dan di lingkungan reaktor RRI-50. Tahapan awal penelitian adalah perhitungan kuat sumber dan inventori bahan radioaktif teras reaktor dengan mensimulasikan operasi 50 MW selama 20 hari tiap siklus menggunakan program ORGEN2.1. Berdasarkan kuat sumber tersebut dan model yang dibuat menggunakan program VisEd, maka dilakukan analisis penentuan parameter perisai radiasi secara iteratif menggunakan program MCNPX. Pada tahap akhir, dilakukan analisis distribusi laju dosis di seluruh ruang di dalam dan di luar gedung reaktor juga menggunakan program MCNPX. Hasil yang diperoleh menunjukkan bahwa ketinggian permukaan air adalah 1000 cm dan kombinasi 90 cm beton berat dan 60 cm beton biasa dapat digunakan sebagai perisai biologi. Desain perisai tersebut mereduksi laju dosis menjadi 0,05 µSv/jam di Balai Operasi sementara di Balai Eksperimen dan di luar gedung reaktor menjadi 4,2 µSv/jam dan 0,03 µSv/jam pada saat reaktor beroperasi. Hasil penelitian juga menunjukkan pemasagan perisai tambahan setebal 280 cm berjarak 300 cm di depan tabung berkas neutron radial yang terbuka mereduksi laju dosis gamma dan neutron menjadi 3,3 µSv/jam dan 3,1x10 -11 µSv/jam. Hasil-hasil penelitian ini menunjukkan bahwa desain perisai radiasi yang dibuat membuat reaktor RRI-50 menjadi aman dari bahaya radiasi bagi pekerja dan masyarakat sekitarnya.Kata kunci : Perisai radiasi, laju dosis, keselamatan radiasi, RRI-50. ABSTRACT RADIATION SHIELDING CONSEPTUAL DESIGN OF RRI-50 REACTOR. One of the parameters that must be met in the design of nuclear reactors is radiation shielding design to ensure the security and safety of workers and the surrounding community. This study has been conducted to design radiation shielding of RRI-50 with high density U9Mo-Al fuel elements that consist of 21 pieces of plate type fuel elements with dimension as same as RSG-GAS fuel elements but the active length is 70 cm. Core configurations consist of 16 fuel elements and 4 control elements and 5 irradiation positions to form a matrix of 5 x 5. The objective of this research is to design radiation shielding and determine the distribution of dose rates in the working

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Neutron shielding qualities and gamma ray buildup factors of concretes containing limonite ore

Cited by 68 publications

References 28 publications

Soft synthesis and characterization of goethite-based nanocomposites as promising cyclooctene oxidation catalysts

Soft synthesis and characterization of goethite-based nanocomposites as promising cyclooctene oxidation catalysts

Coconut Dust Gypsums Board Building Material for Shielding Radiation and Buildup Factors

Desain Konseptual Perisai Radiasi Reaktor Rri-50

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